• 제목/요약/키워드: Waste-to-Energy

검색결과 2,705건 처리시간 0.032초

Solar Energy를 이용한 하수처리의 질소 제거에 관한 연구 (A Study on Removal of Nitrogen at Sewage Treatment using Solar Energy)

  • 황용하
    • 융복합기술연구소 논문집
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    • 제1권2호
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    • pp.37-42
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    • 2011
  • The purpose of this research is to improve nitrogen removal efficiency in winter season through rise of water temperature of extraneous water by using solar energy which is estimated to have great potential among new regeneration energy and while operating Plug-Flow Reactor to improve nitrogen removal efficiency by selecting A/O process among sewage waste water treatment processes as the necessity of solving the problem of nitrogen removal efficiency according to reduced water temperature in winter season and strengthening of water quality criteria regarding discharged sewage waste water suggested in the research background. Summarizing the research result, supply of solar energy source improves the function outstandingly when removing nitrogen, (nitrogen removal rate before operating solar energy 55.4% ${\rightarrow}$ nitrogen removal rate after operating solar energy 84.1%).

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VOLUME REDUCTION OF DISMANTLED CONCRETE WASTES GENERATED FROM KRR-2 AND UCP

  • Min, Byung-Youn;Choi, Wang-Kyu;Lee, Kune-Woo
    • Nuclear Engineering and Technology
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    • 제42권2호
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    • pp.175-182
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    • 2010
  • As part of a fundamental study on the volume reduction of contaminated concrete wastes, the separation characteristics of the aggregates and the distribution of the radioactivity in the aggregates were investigated. Radioisotope $^{60}Co$ was artificially used as a model contaminant for non-radioactive crushed concrete waste. Volume reduction for radioactively contaminated dismantled concrete wastes was carried out using activated heavy weight concrete taken from the Korea Research Reactor 2 (KRR-2) and light weight concrete from the Uranium Conversion Plant (UCP). The results showed that most of the $^{60}Co$ nuclide was easily separated from the contaminated dismantled concrete waste and was concentrated mainly in the porous fine cement paste. The heating temperature was found to be one of the effective parameters in the removal of the radionuclide from concrete waste. The volume reduction rate achieved was above 80% for the KRR-2 concrete wastes and above 75% for the UCP concrete wastes by thermal and mechanical treatment.

배열 이용형 흡수식 사이클 특성평가 (Characteristics Evaluation of Absorption Cycles using the Waste Heat)

  • 윤정인;권오경;문춘근
    • 태양에너지
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    • 제18권4호
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    • pp.23-32
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    • 1998
  • Fuel cells supply electric power and heat at work, and their exhaust gas is comparatively clear. So they are in the limelight as one of the co-generation systems which behave friendly with the environment. Fuel cells discharge both steam and hot water. Accordingly, if we combine absorption heat pump driven by waste heat with fuel cells, we can construct an advanced energy conserving system. The purpose of this study is the objective for evaluating the possibilities of effectively utilizing waste heat of fuel cells as a heat source for the single and double effect absorption systems. Simulation studies on single and double effect absorption have been performed for water/lithium-bromide pair. The effectiveness of introducing a waste heat source of fuel cells is demonstrated. The result of this study showed that total efficiency was about 85% at rated operation and about 75% at 75% load operation. Absorption cycle moved to more strong concentration when fuel cell operated at 75% load.

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UTILIZATION OF ENGINE-WASTE HEAT FOR GRAIN DRYING IN RURAL AREAS

  • Abe, A.;Basunia, M.A.
    • 한국농업기계학회:학술대회논문집
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    • 한국농업기계학회 1996년도 International Conference on Agricultural Machinery Engineering Proceedings
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    • pp.957-966
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    • 1996
  • An attempt was made to measure the availability of waste heat, released from the cooling system of a small engine, which can be utilized for grain drying. An engine powered flat-bed rough rice dryer was constructed and the performance of the dryer with available engine-waste heat was analyzed for 10 , 20, 30 and 40 cm rough rice bulk depths with a constant dryer base area of 0.81$m^2$/min. The waste heat was sufficient to increase the drying air temperature 7 to 12$^{\circ}C$ at an air flow rate of 8.8 to 5.7㎥/min, while the average ambient temperature and relative humidity were 24$^{\circ}C$ and 70%. The minimum energy requirement was 3.26 MJ/kg of water removed in drying a 40 cm deep grain bed in 14h. A forty to fifty centimeter deep grained seems to be optimum in order to avoid over-drying in the top layers. On the basis of minimum energy requirement (3.26 MJ/kg ) , an estimation was made that the waste heat harvest from an engine of a power range of 1 to 10.5PS can dry about 0.1 to 1 metric on of rough rice from 23% to 15% m.c. (w.b) in 12 h at an average ambient temperature and relative humidity of $25^{\circ}C$ and 80%, respectively. The engine-waste heated grain dryer can be used in the rural areas of non industrialized countries where electricity is not available.

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한국원자력연구원 지하처분연구시설 (KAERI Underground Research Tunnel (KURT))

  • 조원진;권상기;박정화;최종원
    • 방사성폐기물학회지
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    • 제5권3호
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    • pp.239-255
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    • 2007
  • 고준위폐기물 기준처분시스템의 건전성과 처분안전성의 실험적 검증에 필수적 시설인 지하처분연구시설이 한국원자력연구원 부지 내에 건설되었다. 지하처분연구시설의 부지조사 결과에 대해 기술하고, 이 부지에 건설될 지하처분연구시설의 설계, 인허가, 건설 과정과 건설된 시설의 개요에 대해 하였다. 또 지하처분연구시설에서 수행 중인 현장실험에 대해 소개하였다.

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Parametric Study for Structural Reinforcement Methods of Disposal Container for NPP Decommissioning Radioactive Waste

  • Hyungoo Kang;Hoseog Dho;Jongmin Lim;Yeseul Cho;Chunhyung Cho
    • 방사성폐기물학회지
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    • 제21권3호
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    • pp.329-345
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    • 2023
  • This paper described a method for analyzing the structural performance of a metal container used for disposing radioactive waste generated during the decommissioning of a nuclear power plant, and numerical analysis results of a method for reinforcing the container. The containers to be analyzed were those that can be used in near-surface and landfill disposal facilities scheduled to be operated at the Gyeongju radioactive waste disposal facility. Structural reinforcement of the container was performed by lattice reinforcement, column reinforcement, and bottom plate reinforcement. Accordingly, a total of 14 reinforcement cases were modeled. The external force causing damage to the container was set equivalent to the impact of a 9-m fall, accounting for the height of the vault at the near-surface disposal facility. The reinforcement methods with a high contribution to the structural performance of the container were concluded to be lattice and column reinforcements.

A Study on the Radio-activity Reduction Method for the Decladding Hull

  • Kim, Jong-Ho;Jung, In-Ha;Park, Jang-Jin;Shin, Jin-Myeong;Lee, Ho-Hee;Yang, Myung-Seung
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
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    • pp.130-139
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    • 2004
  • The cladding materials remaining after reprocessing process of the nuclear fuel, generally called as hulls, are classified as a high-level radioactive waste. They are usually packaged in the container for disposal after being compacted, melted, or solidified into the matrix. The efforts to fabricate a better ingot for a more favorable disposal to the environment have failed due to the technical difficulties encountered in the chemical decontamination method. In the early 1990s, the accumulation of radio-chemical data on hulls and the advent of new technology such as a laser or plasma have made the pre-treatment of the hulls more efficient. This paper summarizes the information regarding the radio-chemical analysis of the hull through a literature survey and determines the characteristics of the hull and depth profile of the radio-nuclides within the hull thickness. The feasibility study was carried out to evaluate the reduction of the radioactivity by peeling off the surface of the hull with the application of laser technology.

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U/RE Recovery Using Large-Scale LCC Electrowinning System

  • Kim, Si Hyung;Shim, Joon-Bo;Jang, Junhyuk;Kwon, Sang-Woon;Lee, Young Sang;Kwon, Youngwoo;Kim, Gha-Young;Lee, Sung-Jai
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2018년도 춘계학술논문요약집
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    • pp.53-54
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    • 2018
  • U/RE was electrochemically recovered to LCC at $50mA/cm^2$ from LiCl-KCl salt containing $0.5wt%UCl_3$, $0.22wt%NdCl_3$, 0.15wt%$CeCl_3$ and $0.07wt%LaCl_3$. The Cd in the LCC deposit was removed during the distillation using Cd distiller. U/RE product of 107g obtained from the distiller was installed to TG and then heated to $1200^{\circ}C$ to be consolidated. Dense U/RE metal ingot was not acquired through the consolidation process because U/RE product had been partially already oxidized during the distillation process.

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Characterization of Groundwater Colloids From the Granitic KURT Site and Their Roles in Radionuclide Migration

  • Baik, Min-Hoon;Park, Tae-Jin;Cho, Hye-Ryun;Jung, Euo Chang
    • 방사성폐기물학회지
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    • 제20권3호
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    • pp.279-296
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    • 2022
  • The fundamental characteristics of groundwater colloids, such as composition, concentration, size, and stability, were analyzed using granitic groundwater samples taken from the KAERI Underground Research Tunnel (KURT) site by such analytical methods as inductively coupled plasma-mass spectrometry, field emission-transmission electron microscopy, a liquid chromatography-organic carbon detector, and dynamic light scattering technique. The results show that the KURT groundwater colloids are mainly composed of clay minerals, calcite, metal (Fe) oxide, and organic matter. The size and concentration of the groundwater colloids were 10-250 nm and 33-64 ㎍·L-1, respectively. These values are similar to those from other studies performed in granitic groundwater. The groundwater colloids were found to be moderately stable under the groundwater conditions of the KURT site. Consequently, the groundwater colloids in the fractured granite system of the KURT site can form stable radiocolloids and increase the mobility of radionuclides if they associate with radionuclides released from a radioactive waste repository. The results provide basic data for evaluating the effects of groundwater colloids on radionuclide migration in fractured granite rock, which is necessary for the safety assessment of a high-level radioactive waste repository.

폐FRP 선박으로부터 섬유보강재 추출공정 개선 연구 (Developing a Study on the Extracting Method of Laminated Glass Fiber from FRP Boats)

  • 윤구영
    • 한국해양환경ㆍ에너지학회지
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    • 제12권1호
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    • pp.23-28
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    • 2009
  • 폐FRP 선박을 재활용하는 기술은 많은 발전을 이루어 왔으며 최근에는 가장 재활용도가 적은 부분인 유리섬유의 고부가치화 재활용이 특히 주목받고 있다. 폐FRP 선박의 재처리 과정에서 추출된 유리섬유는 피막된 수지 성분의 내화학성으로 인하여 섬유보강재로서 사용 가능하다는 것이 보고되었다. 그러나 섬유보강재(laminated glass fiber reinforced material)를 추출하는 공정의 효율성과 경제성의 재고는 개선되어여할 과제이다. 본 연구는 다층구조인 FRP로부터 면포층(roving cloth layer)을 보다 효과적으로 박리할 수 있는 방법을 제시하여 추출공정의 최적화를 도모하고자한다. 새로운 추출공정에서 생산된 섬유보강재를 활용한 섬유강화콘크리트(Fiber Reinforced Concrete, FRC)의 강성은 매우 우수한 것으로 관찰되었다.

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